1CAN049501, Monthly Operating Rept for Mar 1995 for ANO Unit 1

Monthly Operating Rept for Mar 1995 for ANO Unit 1

ML20082K119
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/31/1995
From:	Hayes K, Mims D ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1CAN049501, 1CAN49501, NUDOCS 9504190079
Download: ML20082K119 (7)

Text

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Entsrgy Operations, Inc.

cr~ ENTERGY ma sa 333 RusselMile AR 72801 Tel 501858 5000 April 14,1995 i

a 1CAN049501 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station P1-137 i

Washington, DC 20555 i

Subject:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Monthly Operating Report j

Gentlemen:

The Arkansas Nuclear One - Unit 1 Monthly Operating Report for March 1995 is attached.

This report is submitted in accordance with ANO-1 Technical Specification 6.12.2.3.

Very truly yours,'

I b&piflC.11(d Dwight C. Mims Director, Licensing DCM/dwb 4

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1 9504190079 950331

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l U. S. NRC April 14,1995 1CAN049501 Page 2 i

cc:

Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One 1448 S. R. 333 Russellville, AR 72801 1

1 Mr. George Kalman NRR Project Manager Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Contrnission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 i

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1 OPERATING DATA REPORT i

4 DOCKET NO:

50-313 DATE:

April 14,1995 COMPLETED BY: K. R. Hayes TELEPHONE:

(501) 858-5535 OPERATING STATUS 1.

Unit Name: Arkansas Nuclear One - Unit 1 2.

Reporting Period: March 1-31,1995 3.

Licensed ThermalPower (MWt): 2,568 4.

Nameplate Rating (Gross MWe): 902.74 5.

Design ElectricalRating (Net MWe): 850 6.

Maximum Dependable Capacity (Gross MWe): 883 7.

Maximum Dependable Capacity (Net MWe): 836 i

8.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9.

Power Imel To Which Restricted. If Any (Net MWe): Nonc 10.

Reasons For Restrictions. If Any: None MONTH YR-TO-DATE CUMULATIVE 11.

Hours in Reporting Period.

744.0 2,160.0 177,787.0 12.

Number of Hours Reactor was Critical..

6.7 1,063.9 130,320.1 13.

Reactor Reserve Shutdown Hours.

0.0 0.0 5,044.0 14.

Hours Generator On-Line..

0.0 1,056.4 128,044.4 15.

Unit Reserve Shutdown Hours.

0.0 0.0 817.5 16.

Gross ThermalEnergy Generated (MWH)..

0.0 1,974,132.8 296,128,022.0 17.

Gross ElectricalEnergy Generated (MWH).......

0.0 670,015.0 98,981,935.0 18.

Net ElectricalEnergy Generated (MWH)..

-5,499.0 629,565.0 94,155,262.0 19.

Unit Service Factor.

0.0 48.9 72.0 20.

Unit AvailabilityFactor.

0.0 48.9 72.5 21.

Unit Capacity Factor (Using MDC Net)..

-0.9 34.9 63.3 22.

Unit Capacity Factor (Using DER Net) -

-0.9 34.3 62.3 23.

Unit Forced Outage Rate........

0.0 0.0 10.6

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24.

Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

25.

If Shut Down At End of Report Period. Estimated Date of Startup:

April 7,1995 26.

Units in Test Status (Prior to Commercial Operation):

i Forecast Achieved INITIAL CRITICALITY 08/06n4 INITIAL ELECTRICITY 08/17n4 COMMERCIAL OPERATION 12/19n4 l

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AVERAGE DAILY UNIT POWERLEVEL DOCKET NO:

50-313 UNIT:

One DATE:

April 14,1995 COMPLETED BY: K. R. Hayes TELEPHONE:

(501) 858-5535 1

MONTH March 1995 j

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DAY AVERAGE DAILY POWER LEVEL

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(MWe-Net) 1 1.......

-4

)

2

-4 4

3

-4 i

4 4

5

-4 i

6.......

-4 5

7...............

-4 I

8.

-4 a

9.

4 10.

-5 4

11-.

-4 l

12

-5 13..

-5 a

j 14..

-4 15.

3 1

16.

-4

-4

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17.

18.

-4 19.......

-5 20....

-5 i

21.....

-7 22.

-6 23..

-7 3

24.

-7 25..

-7 26..

-8 1

27.

-8 1

2 8......

-8 29...

-22 30.

-33

31..

-33 AVGS:

-7 INSTRUCTION 1

.I On this format, list the average daily unit power level in MWe-Net for each day in reporting month. Complete to the nearest whole megawatt.

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.m m..

m.

UNIT SHUTDOWNS AN3 POWER REDUCTIONS REPORT FOR M:rth 1995 DOCKET NO.

50-313 UNIT NAME ANO Unit 1

• DATE April 14,1995 COMPLETED BY K. R. Hayes TELEPHONE 501-858-5535 METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE A CORRECTIVE ACTION TO M

DATF, TYPE' (HOURS)

REASON 2 REACTORS REPORT #

CODE' CODE' PREVENT RECURRENCE 95-02 950214 S

359.6 C

4 N/A -

N/A N/A Refueling Outage IR12 4

1 2

3 4

F: Forced Reason:

Method:

Exhibit G -Instructions S: Scheduled A-Equipment Failure (Explain) 1 - Manual for Preparation of Data B - Maintenance of Test 2 - Manual Scram.

Entry Sheets for Ucensee C-Refueling 3 - Automatic Scram.

Eveet Report (LER) File (NUREG-9161)

D - Regulatory Restriction 4 - Continuation E-Operator Training A Ucense Examination 5 -Imad Reduction F-Administration 9 - Other

'5 G - Operational Error Exhibit I-Same Source H - Other (Explain) l

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I NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

4 MARCH 1995 i

UNIT ONE i

J Arkansas Nuclear One, Unit One, began the month in Refueling Outage IR12.' The unit remained offline for this refueling outage for the entire month.

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i Reporting Period: March 1995 -

REFUELING INFORMATION 1.

Name of facility: Arkansas Nuclear One - Unit 1 2.

Scheduled date for next refueling shutdown: Entered refuelina outane 1R12 on Fetraarv 14c 1995 3.

Scheduled date for restart following refueling: Anril 7.1995 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? If answer is yes, what, in general, will there be? If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Comnuttee to deternune whether any unreviewed safety questions are associated with the core reload (Ref.10CFR Section 50.59)?

Yn 5.

Scheduled date(s) for submitting proposed licensing action and supporting information:

All license amendments received and aooroved.-

6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

None olanned 7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:'

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a) 171 b)241 8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that hadeen requested or is planned, in number of fuel assemblies:

present 268 increase size by 0 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

DATE:

1226 (Loss of full core off-load capability)

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